US3603634A - Centering device for nuclear reactor loading machines - Google Patents

Centering device for nuclear reactor loading machines Download PDF

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Publication number
US3603634A
US3603634A US764526A US76452668A US3603634A US 3603634 A US3603634 A US 3603634A US 764526 A US764526 A US 764526A US 76452668 A US76452668 A US 76452668A US 3603634 A US3603634 A US 3603634A
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US
United States
Prior art keywords
fuel element
tubular member
centering device
fuel elements
mast
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Lifetime
Application number
US764526A
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English (en)
Inventor
Hermann Kumpf
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Siemens AG
Siemens Corp
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Siemens Corp
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Filing date
Publication date
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Publication of US3603634A publication Critical patent/US3603634A/en
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/16—Articulated or telescopic chutes or tubes for connection to channels in the reactor core
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S294/00—Handling: hand and hoist-line implements
    • Y10S294/906—Atomic fuel handler

Definitions

  • Centering device in a machine for loading fuel elements in a nuclear reactor having a movable vertical tubular loading mast and a fuel element clamping device movable in the mast interior includes a tubular member located at and telescoping the lower end of the mast and being displaceable in the longitudinal direction thereof so as to telescope a fuel element selected from a multiplicity of fuel elements forming a reactor core.
  • the tubular member has a lower edge portion formed with a surface engageable with the fuel elements ofthe reactor core located adjacent the selected fuel element so as to align the latter with the mast.
  • My invention relates to a centering device for a fuel-element-loading machine employed for charging and discharging fuel elements in a pressurized or boiling water nuclear reactor.
  • the loading machine is of the known type which is secured to a travelling crane and adjustable in the vertical direction thereon, and is capable of travelling in two coordinate directions above a reactor core formed of a multiplicity of fuel elements and above a settling tank for the replaced radioactive fuel elements.
  • This conventional type of loading machine comprises a tubular loading mast as well as a fuel element clamping device mounted for displacement in the interior of the tubular loading mast.
  • an exceptionally accurate and delicately sensitive operating drive means for the fuel-element-replacing machine is required whereby the initial positioning of the respective fuel element is so accurate that the fuel element can be withdrawn from the position thereof without any mechanical obstruction or hindrance.
  • a centering device comprising a tubular member located at and telescoping the lower end of the tubular loading mast and being displaceable in the longitudinal direction thereof so as to be placed on a selected fuel element, the tubular member having a lower edge portion formed with a surface engageable with other fuel elements of the reactor core adjacent the selected fuel element so as to align the selected fuel element with the tubular loading mast.
  • the surface engageable with the fuel elements is conical.
  • FIG. 1 is a diagrammatic elevational view of the centering device of my invention as used in conjunction with a loading machine for exchanging fuel elements from a nuclear reactor;
  • FIGS. 2 and 3 are a plan view and a fragmentary elevational view, respectively, of the bottom end of a modified embodiment of the centering device shown in FIG. 1.
  • the reactor pressure vessel, the control devices and other conventional equipment of a pressurized or boiling water reactor have been omitted from the drawing.
  • the reactor core is represented by only four fuel elements 1 which are shown immersed in coolant having a surface level 2.
  • the reactor represented in FIG. 1 can be either of the boiling water or pressurized water types.
  • the carriage 4 has a boom 43 which carries a device 41 of conventional construction for holding and raising a hollow tubular loading mast 5 in vertical direction as shown by the associated double-headed arrow, and also carries at the free end thereof a hoisting unit 42 for a fuel-element-clamping device 6 which is located in the interior of the hollow loading mast 5 above a respective fuel element 1.
  • the loading mast 5 is able to be moved in two horizontal coordinate directions, namely in the directions of the crane bridge 3 as exemplified by the horizontally extending double-headed arrow as well as in the direction of the trolley carriage 4, Le. in a direction perpendicular to the plane of the drawing of FIG. 1, so that it can thereafter be lowered telescopingly above each fuel element position.
  • the loading mast 5 is provided with a centering device 7, in accordance with my invention, which has a tubular shape and which is so mounted telescopingly on the lower end of the loading mast 5 as seen in FIG. 1 as to be displaceable between a pair of stop rings 51 suitably mounted on the outside of the loading mast 5.
  • the centering device 7 has an enlarged lower edge 72 as shown in FIG. 1 which, in the illustrated embodiment, has a conical shape and which, when telescopingly placed on a selected fuel element 1, is automatically centered with respect to the selected fuel element I which is surrounded thereby,
  • the conical or tapering surfaces of the lower edge 72 of the centering device 7 are slidable for this purpose along the suitably shaped conical or inclined surfaces 12 of the fuel elements in a downward direction and thereby dispose the loading mast 5 so that it is located accurately above the selected fuel element 1 which is to be clamped by the clamping device 6 and removed from the reactor core.
  • the fuel elements 1 which are located adjacent to the selected fuel element, which is to be removed from the reactor core, are simultaneously forced slightly in a lateral direction so that the fuel element to be exchanged is clamped at its gripping knob 11, located at an end thereof, by the aforementioned clamping device 6 which is carried by a sliding carriage displaceable along the interior of the loading mast 5 on roller bearings 61.
  • the fuel element which is to be replaced is then drawn upwardly by the hoisting unit 42.
  • the centering device generally having the square-shaped cross section such as shown in FIGS. 2 and 3 can be used in conjunction with the loading device for replacing these fuel elements.
  • Such fuel elements conventionally are provided with a sheet metal cladding which can be formed with a plurality of nonillustrated bores solely for permitting penetration thereof by the surrounding coolant.
  • fuel elements have also become available which do not have this so-called box about them and which are not provided with any outer sheet metal cladding of this type.
  • Such fuel elements are held together only by suitable construction of spacer members within the reactor core or by special structural elements as is well known in the art.
  • the fuel elements located adjacent to the fuel element being exchanged are forced slightly away in lateral directions when removing or inserting a fuel element, to an extent determined by the play or clearance provided in the construction thereof, so that mutual jamming or binding of these fuel elements with the fuel element being exchanged is thereby safely avoided.
  • the centering device 7 can be desirable, however, to force the centering device 7 by means of a conventional pressure-exerting device 44, for example of hydraulic type, deeper between the fuel element being removed or replaced and the adjacent fuel elements of the reactor core in order to provide thereby even greater space therebetween to permit removal of the respective fuel element telescopingly surrounded by the centering device 7, without the entrainment of any of the adjacent fuel elements and raising of the same therewith.
  • the lifting device 41 which can have a construction, for example, similar to the lifting mechanism ofa mechanical jack, the centering device 7 which then rests at its upper end as shown in H0. l against the lower stop ring 51 is simultaneously raised therewith and removed from the reactor core. Friction between the loading mast 5 and the centering device 7 is preferably reduced by means of rollers 71 to the smallest possible value.
  • the lower edge of the centering device 7, as viewed in FIG. 1, can be given any suitable desired cross-sectional shape.
  • a centering device comprising a tubular member located at and telescoping the lower end of the tubular loading mast and being displaceable together therewith in the longitudinal direction thereof, so as to be placed on a selected fuel element, said tubular member having an enlarged lower edge portion formed with a downwardly inclined surface engageable with fuel elements adjacent the selected fuel element so as to force the adjacent fuel elements aside and align the selected fuel element with the tubular loading mast.
  • centering device wherein said lower edge portion of said tubular member has a thickness greater than the spacing between the fuel elements of the reactor core, said tubular member being displaceable by force of gravity downwardly about a selected fuel element to be removed from the reactor core so as to be disposed in the space between the selected fuel element and the adjacent fuel elements surrounding it, whereby the adjacent fuel elements are laterally displaced so as to facilitate removal of the selected fuel element.
  • centering device wherein said lower edge portion of said tubular member has a thickness greater than the spacing between the fuel elements of the reactor core, and including means for forcibly displacing said tubular member downwardly about a selected fuel element to be removed from the reactor core so as to be disposed in the space between the selected fuel element and the adjacent fuel elements surrounding it, whereby the adjacent fuel elements are laterally displaced so as to facilitate removal of the selected fuel element.
  • Centering device wherein said displacing means is a hydraulic pressure device operatively connected to said tubular member.
  • Centering device including at least one slit formed in said lower edge portion of said tubular member for observing the selected fuel element received therein.
  • Centering device including a plurality of slits uniformly spaced about the peripheral surface of said lower edge portion.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
US764526A 1968-07-15 1968-10-02 Centering device for nuclear reactor loading machines Expired - Lifetime US3603634A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR159247 1968-07-15

Publications (1)

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US3603634A true US3603634A (en) 1971-09-07

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US (1) US3603634A (enrdf_load_stackoverflow)
FR (1) FR1581073A (enrdf_load_stackoverflow)

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2373858A1 (fr) * 1976-12-07 1978-07-07 Westinghouse Electric Corp Appareil de manutention de combustible nucleaire
FR2588689A1 (fr) * 1985-10-11 1987-04-17 Fragema Framatome & Cogema Machine de manutention d'assemblage combustible nucleaire et procede de chargement de reacteur en comportant application
US4676945A (en) * 1984-12-20 1987-06-30 Exxon Nuclear Company, Inc. Fuel assembly insertion system
FR2593598A1 (fr) * 1986-01-27 1987-07-31 Framatome Sa Procede et dispositif de controle de la verticalite du mat de manutention d'une machine
US5084230A (en) * 1990-12-12 1992-01-28 Westinghouse Electric Corp. Hand held tool for removing and replacing a removable top nozzle
US5898745A (en) * 1997-10-07 1999-04-27 Framatome Technologies, Inc. Nuclear fuel assembly locator
FR2848328A1 (fr) * 2002-12-10 2004-06-11 Framatome Anp Procede et dispositif de chargement d'un assemblage de combustible dans le coeur d'un reacteur nucleaire.
WO2022017880A1 (en) * 2020-07-23 2022-01-27 Rolls-Royce Plc Nuclear refuelling device

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3600277A (en) * 1968-10-02 1971-08-17 Atomic Energy Commission Refueling apparatus and method for fast reactors
US4236966A (en) * 1977-11-30 1980-12-02 Savin Nikolai I Nuclear reactor

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2924483A (en) * 1957-03-19 1960-02-09 Leonard J Koch Fuel handling mechanism
US3124260A (en) * 1959-03-09 1964-03-10 Data storage
US3126008A (en) * 1959-02-09 1964-03-24 Data storage access mechanism

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2924483A (en) * 1957-03-19 1960-02-09 Leonard J Koch Fuel handling mechanism
US3126008A (en) * 1959-02-09 1964-03-24 Data storage access mechanism
US3124260A (en) * 1959-03-09 1964-03-10 Data storage

Cited By (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2373858A1 (fr) * 1976-12-07 1978-07-07 Westinghouse Electric Corp Appareil de manutention de combustible nucleaire
US4676945A (en) * 1984-12-20 1987-06-30 Exxon Nuclear Company, Inc. Fuel assembly insertion system
FR2588689A1 (fr) * 1985-10-11 1987-04-17 Fragema Framatome & Cogema Machine de manutention d'assemblage combustible nucleaire et procede de chargement de reacteur en comportant application
EP0220117A1 (fr) * 1985-10-11 1987-04-29 Framatome Machine de manutention d'assemblage combustible nucléaire et procédé de chargement de réacteur en comportant application
US4788028A (en) * 1985-10-11 1988-11-29 Framatome Machine and method for handling a nuclear fuel assembly
FR2593598A1 (fr) * 1986-01-27 1987-07-31 Framatome Sa Procede et dispositif de controle de la verticalite du mat de manutention d'une machine
US5084230A (en) * 1990-12-12 1992-01-28 Westinghouse Electric Corp. Hand held tool for removing and replacing a removable top nozzle
US5898745A (en) * 1997-10-07 1999-04-27 Framatome Technologies, Inc. Nuclear fuel assembly locator
FR2848328A1 (fr) * 2002-12-10 2004-06-11 Framatome Anp Procede et dispositif de chargement d'un assemblage de combustible dans le coeur d'un reacteur nucleaire.
WO2004064076A3 (fr) * 2002-12-10 2004-08-26 Framatome Anp Procede et dispositif de chargement d'un assemblage de combustible dans le coeur d'un reacteur nucleaire
US20060034413A1 (en) * 2002-12-10 2006-02-16 Framatome Anp Method and device for loading a fuel assembly into the core of a nuclear reactor
US7386087B2 (en) 2002-12-10 2008-06-10 Framatome Anp Method and device for loading a fuel assembly into the core of a nuclear reactor
CN100495584C (zh) * 2002-12-10 2009-06-03 法玛通Anp公司 用于将燃料组件装入到核反应堆中的方法和装置
WO2022017880A1 (en) * 2020-07-23 2022-01-27 Rolls-Royce Plc Nuclear refuelling device
US20230298775A1 (en) * 2020-07-23 2023-09-21 Rolls-Royce Plc Nuclear refuelling device

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Publication number Publication date
FR1581073A (enrdf_load_stackoverflow) 1969-09-12

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